Pages that link to "LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-1 Through K-75"
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The following pages link to LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-1 Through K-75:
Displayed 50 items.
- ML102790106 (← links)
- LR-N10-0306, 50.59 Review Coversheet Form for Hope Creek Unit 1 DCP 80102144, Revise Dose Analysis Calculations & Update UFSAR to Remove 120 Second Isolation Time for Pciv'S (← links)
- LR-N10-0239, 0000-0119-1728, Revision 0, Hope Creek Cycle 17 Stability Results for GE14i Support, Attachment 1 (← links)
- ML101390318 (← links)
- LR-N08-0224, Attachment 6 - Hope Creek Final Stress Assessment of Hope Creek, Unit 1 Steam Dryer at 115% CLTP Conditions, C.D.I. Report No. 08-21NP, Revision 1 (← links)
- LR-N08-0224, Attachment 5 - Limit Curves with ACM Rev. 4 for 115% Power Level Basis at Hope Creek, Unit 1, C.D.I. Technical Note No. 08-22NP, Revision 0 (← links)
- ML083100828 (← links)
- LR-N08-0224, Attachments 3 and 4 - Hope Creek Extended Power Uprate Power Ascension Test Report and Affidavit (← links)
- ML083100827 (← links)
- ML082600573 (← links)
- LR-N08-0199, Attachment 5 - C.D.I. Report.No. 08-29NP, Rev. 0, Final Stress Assessment of Hope Creek Unit 1 Steam Dryer at 111.5% CLTP Conditions. (← links)
- LR-N08-0199, Attachment 4 - C.D.I. Technical Note No. 08-20NP, Rev. 1, Limit Curves with ACM Rev. 4 for 111.5% Power Level Basis at Hope Creek Unit 1. (← links)
- ML082540329 (← links)
- ML082110419 (← links)
- LR-N08-0123, C.D.I. Technical Note No. 07-29NP, Revision 2, Limit Curve Analysis with ACM Rev. 4 for Power Ascension at Hope Creek Unit 1. (← links)
- ML081360492 (← links)
- ML080420544 (← links)
- LR-N08-0033, CDI Report No. 07-17NP, Revision 4, Stress Assessment of Hope Creek Unit I Steam Dryer Based on Revision 4 Loads Model. (← links)
- LR-N07-0298, C.D.I. Report No. 04-09NP, Revision 6, Methodology to Determine Unsteady Pressure Loading on Components in Reactor Steam Domes. (← links)
- ML073230096 (← links)
- ML072640411 (← links)
- ML071720370 (← links)
- ML071700217 (← links)
- ML071450114 (← links)
- ML071360377 (← links)
- ML071290574 (← links)
- ML070871108 (← links)
- ML070871106 (← links)
- ML070810365 (← links)
- LR-N07-0034, C.D.I. Technical Memorandum No. 06-23NP, Revision 1, Comparison of the Hope Creek and Quad Cities Steam Dryer Loads at EPU Conditions. (← links)
- LR-N06-0392, WCAP-16640-NP, Steam Generator Alternate Repair Criteria for Tube Portion within the Tubesheet at Salem Unit 1. (← links)
- ML062920093 (← links)
- ML062280556 (← links)
- ML062230319 (← links)
- ML050060041 (← links)
- LR-N13-0172, Enclosure 1 - Salem Nuclear Generating Station Unit 1 Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic (← links)
- LR-N13-0020, SL-011677, Rev 3, Reliable Spent Fuel Pool Instrumentation Overall Integrated Plan (← links)
- LR-N09-0232, WCAP-17071-NP, Rev. 0, H*: Alternate Repair Criteria for the Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model F). (← links)
- ML18337A326 (← links)
- ML18337A325 (← links)
- ML18337A324 (← links)
- LR-N13-0122, Steam Generator Tube Inspection Report - Nineteenth Refueling Outage (2R19) (← links)
- LR-N10-0153, Submittal of Steam Generator Tube Inspection Report - Seventeenth Refueling Outage (2R17) (← links)
- LR-N08-0043, Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. (← links)
- LR-N07-0265, Steam Generator Tube Inspection Report Eighteenth Refueling Outage (1R18) (← links)
- LR-N07-0016, Inservice Inspection Activities - 90-Day Report (← links)
- LR-N06-0180, Special Report, Main Steam Line Monitor Inoperable Greater than 7 Days (← links)
- ML071630307 (← links)
- ML071290567 (← links)
- ML071290563 (← links)